Text

Issuance of Amendments 247 & 250, 1.62% Increase in Licensed Power Level
	ML031010365
Person / Time
Site:	Peach Bottom ; (DPR-044, DPR-056)
Issue date:	11/22/2002
From:	Boska J; NRC/NRR/DLPM/LPD1
To:	Skolds J; Exelon Generation Co, Exelon Nuclear
References
	TAC MB5192, TAC MB5193
	Download: ML031010365 (32)
	v • d • e

November 22, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: 1.62% INCREASE IN LICENSED POWER LEVEL (TAC NOS. MB5192 AND MB5193)

Dear Mr. Skolds:

The Commission has issued the enclosed Amendments Nos. 247 and 250 to Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3.

These amendments consist of changes to the Facility Operating License and Technical Specifications in response to your application dated May 24, 2002, as supplemented by letters dated June 27, September 11, September 24, and October 16, 2002.

These amendments increase the licensed power level by approximately 1.62% from 3458 megawatts thermal (MWt) to 3514 MWt. These changes are based on increased feedwater flow measurement accuracy achieved by utilizing high accuracy ultrasonic flow measurement instrumentation.

A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

John P. Boska, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation 50-277 and 50-278

1. Amendment No. 247 to DPR-44

2. Amendment No. 250 to DPR-56 Docket Nos.

Enclosures:

3. Safety Evaluation cc w/encds: See next page DISTRIBUTION:

PUBLIC PDI-2 R/F SRichards MShuaibi CHolden NTrehan RCaruso GThomas SCoffin MReinhart FAkstulewicz LLois BPlatchek, RI SWeerakkody EWeiss JAndersen EMarinos MMitchell GHill (4)

DTrimble JBoska MWaterman KManoly RDennig JTappert MO'Brien SWall LLund YDiaz KChang JLee ACRS AHodgdon, OGC Package No:

Acressinn Nno.

SE input provided - no major changes made.

- See Drevious concurrence Ak~w<IIIVI l

SV................---r----

OFFICE PD1-2/PM PDI-2/LA EMCB/SC' EMCB/SC^ SRXB/SC0 SRXBI/SC* EMEB/SC SPSB/SC*

EEIBI/SC*

NAME JBoska MO'Brien ILLund SCoffin FAkstulewicz RCaruso KManoly MReinhart CHolden DATE 111/21/02 111/21/02 110/04/02 10/03/02 109/25/02 110/07/02 110/12/02 09/23/02 10/03/02 OFFICE EEIB/SC*

RLEP/SC** IEHB/SC**

SPLB/SC** SPLB/SC**

OGC**

PD1-2/(A)SC PD1ID DLPM/(A)D NAME EMarinos JTappert DTrimble EWeiss SWeerakkody AHodgdon JAndersen SRichards LMarsh DATE 10/17/02 10/31/02 11/15/02 11/14/02 11/14/02 11/21/02 11/21/02 11/22/02 11/22/02 OFFICIAL RECORD COPY

November 22, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT RE: 1.62% INCREASE IN LICENSED POWER LEVEL (TAC NOS. MB5192 AND MB5193)

Dear Mr. Skolds:

The Commission has issued the enclosed Amendments Nos. 247 and 250 to Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3.

These amendments consist of changes to the Facility Operating License and Technical Specifications in response to your application dated May 24, 2002, as supplemented by letters dated June 27, September 11, September 24, and October 16, 2002.

These amendments increase the licensed power level by approximately 1.62% from 3458 megawatts thermal (MWt) to 3514 MWt. These changes are based on increased feedwater flow measurement accuracy achieved by utilizing high accuracy ultrasonic flow measurement instrumentation.

A copy of the safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely, IRA!

John P. Boska, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosures:

1. Amendment No. 247 to DPR-44

2. Amendment No. 250 to DPR-56

3. Safety Evaluation cc w/encls: See next page

EXELON GENERATION COMPANY. LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 247 License No. DPR-44

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated May 24, 2002, as supplemented by letters dated June 27, September 11, September 24, and October 16, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to paragraph 2.C.(1) of Facility Operating License No. DPR-44, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(1)

Maximum Power level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

3.

The license is also amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 247, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

4.

This license amendment is effective as of its date of issuance, and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION IRA!

Ledyard B. Marsh, Acting Director Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to Facility Operating License No. DPR-44, page 3, and the Technical Specifications Date of Issuance: November 22, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 247 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Facility Operating License and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Facility Operating License page 3 page 3 Technical Specifications 1.1-5 3.3-2 3.3-6 3.3-7 3.3-8 3.3-31 a 3.3-31 b 3.3-31 c 3.4-5 1.1-5 3.3-2 3.3-6 3.3-7 3.3-8 3.3-31 a 3.3-3 1 b 3.3-31 c 3.4-5

restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)

Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C.

This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

The Surveillance Requirements (SRs) listed in the licensee's letter dated August 4,1995 are not required to be performed Immediately upon implementation of Amendment No. 210. The SRs listed in the licensee's letter dated August 4,1995 shall be successfully demonstrated prior to the time and condition specified below for each:

a)

Those SRs listed as Category A SRs in the licensee's August 4, 1995 letter shall be completed within a period consistent with the implementation date for Amendment 210, the specified frequency for each SR and the allowance of SR 3.0.2; b)

Those SRs listed as Category B SRs in the licensee's August 4, 1995 letter shall be completed within a period consistent with the last completion date for the related existing SRs, the specified frequency for each SR and the allowance of SR 3.0.2.

Page 3 Amendment No. 14,10, 53, 70,135, 194,199,210, 215, 233, 247

Ue T1 r 1 Z or s

1. 1 A1 1.1 Definitions PHYSICS TESTS (continued)

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3514 MWt.

The RPS RESPONSE TIME shall be that time interval from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a.

The reactor is xenon free;

b. The moderator temperature is 680F; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

I STAGGERED TEST BASIS THERMAL POWER A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

(continued)

PBAPS UNIT 2 1.1-5 Amendment No. 2-',

247

,-.Z

!nstrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more automatic C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with RPS capability.

trip capability not maintained.

OR Two or more manual Functions with RPS trip capability not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B, or C not met.

the channel.

E. As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 29.5% RTP.

and referenced in Table 3.3.1.1-1.

F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G.

As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

(continued)

I PBAPS UNIT 2 3.3 -2 Amendment No. 2-1-0, 247

??H lrnstrumenta1ion 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.13 Verify Turbine Stop Valve-Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is

> 29.5% RTP.

SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST.

24 months SR 3.3.1.1.15 Perform CHANNEL CALIBRATION.

24 months SR 3.3.1.1.16 Calibrate each radiation detector.

24 months SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.

PBAPS UNIT 2 3.3-6 Amendment No.

3-9, 247

r

, z Sr rimen: ati on 3 3.3.1.1 Table 3.3 1 1-1 (page 1 of 3)

Reactor Protection System Instrumentation CUNUI I 1UN

APPLICABLE MODES OR OTHER SPECIFIED rnDnITInNS REQUIRED CHANNELS PER TRIP SYSTEM REFERENCED FROM REQUIRED ACTION D 1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE rFtUrTIN

.f.1 i i_..

o 1

Wide Range Neutron Monitors

a. Period-Short 5(a) 3 3

3 G

SR SR SR SR SR H

SR SR SR SR SR 3 3 1.1 1 3.3.1.1 5 3.3.1.1 12 3.3.1.1.17 3.3.1 1.18 3.3.1.1.1 3.3.1.1.6 3.3.1. 1.12 3.3.1.1.17 3.3.1.I.18 2 13 seconds 2 13 seconds NA

b.

Inop G

SR 3.3.1.1.5 SR 3.3.1.1.17 5(a) 3 H

SR 3.3.1.1.6 SR 3.3.1.1.17 NA

2.

Average Power Range Monitors

a. Neutron Flux-High (Setdown)

G SR SR SR SR F

SR SR b.

Simulated Thermal Power-High

c.

Neutron Flux-High 1

1 3 (c) 3IC)

F SR SR SR SR SR SR SR SR SR SR SR SR SR 3.3 1.1.1 3.3.1.1.

3.3 1.1.11 3.3.1.1.12 3.3.1.1.1 3.3.1.1.2 3.3.1.1.8 3.3.1.1 11 3.3.1.1.12 3.3.1.1.1 3.3.1.1.2 3.3.1.1.8 3.3.1.1 11 3.3.1. 1. 12 3.3.1.

1. 11 3.3.1.1.1 3.3.1.1.11 3.3.1.1.17 3.3.1.1.18 s l5.OS RTP s 0.65 W

+ 63.7S RTP(b) and < 118.0S RTP s 119.7S RTP I

d.

e.

Inop 2-Out-Of-4 Voter 1.2 1.2 3(C)

G G

NA NA (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.65 W + 63.7S - 0.65 AW RTP when reset for single loop operation Operating.

(c) Each APRM channel provides inputs to both trip systems.

per LCO 3.4.1.

Recirculation Loops I

PBAPS UNIT 2 3.3-7 Amendment No.

247

II I l I, 1 7' 1

=

-,w 3~.3. I 1 Table 3.3 1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED PEFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D 1 REQUIREMENTS VALUE 3

Reactor Pressure -High 1.2 2

G SR 3 3 1 1.1 s 1085 0 psig SR SR SR SR

4.

Reactor Vessel Water Level-Low (Level 3)

5.

Main Steam Isolation Valve -Closure 1.2 1

2 8

G F

SR SR SR SR SR SR SR SR SR 35 31 1.9i 3.3 1 1 15 3.3.1 1.17 3.3.1 1.18 3.3.1.1.1 3.3.1.1.9 3.3.1.1.15 3.3.1 1.17 3.3.1.1.18 3.3.1.1.9 3.3 1.1.15 3.3.1.1.17 3.3

.1.1. 18 a 1.0 inches s 1D closed

6.

Drywell Pressure-High 1.2 G

SR SR SR SR SR

7.

Scram Discharge Volume Water Level -High 1.2 2

2 5(a)

G SR SR SR SR H

SR SR SR E

SR SR SR SR SR 3 3.1.1.1 3.3.1.1 9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 s S0.0 gallons s 50.0 gallons s 2.0 psig

8.

Turbine Stop Valve -Closure 2 29.5S RTP 4

s 10 closed I

9.

Turbine Control Valve Fast Closure. Trip Oil Pressure -Low 2 29.5S RTP E

SR SR SR SR SR

10.

Turbine Condenser-Low Vacuum 1

2 F

SR SR SR SR SR 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.1 3.3.1.1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.1 3.3.1.1.10 3.3.1.1.16 3.3.1.1.17 3.3 1.1.18 2 500.0 psig I

2 23.0 Inches Hg vacuum

11.

Main Steam Line -High Radiation 1.2 2

G SR SR SR SR SR s 15 X Full Power

Background

12.

Reactor Mode Switch -

Shutdown Position 1.2 1

1 G

H SR 3.3.1.1.14 SR 3.3.1.1.17 SR 3.3.1.1.14 SR 3.3.1.1.17 NA 5(a)

(continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

PBAPS UN IT 2 3.3 -8 Amendment No.

210, 247

Li- ~

instrumen atlon 3.3 INSTRUMENTATION 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.2

a.

Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV)-Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure-Low.

OR

b.

The following limits are made applicable:

1. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for inoperable EOC-RPT as specified in the COLR; and

2. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

limits for inoperable EOC-RPT as specified in the COLR.

APPLICABILITY:

THERMAL POWER 2 29.5% RTP.

I ACTIONS NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

OPERABLE status.

OR A.2

NOTE---------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

(continued)

PBAPS UNIT 2 3.3-31a Amendment No.

A2-,

247

uz -r -.

t I

{ ILAIll t II33d X I U 1

3.3.4. 2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with EOC-RPT trip capability.

capability not maintained.

C. Required Action and C.1 Remove the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion recirculation pump Time not met.

from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 29.5% RTP.

SURVEILLANCE REQUIREMENTS NOTE-------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL FUNCTIONAL TEST.

92 days (continued)

PBAPS UNIT 2 3.3-31 b Amendment No. 2-2-5,247

- -' -r, i.nscru eflelnat Ol 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL CALIBRATION. The 24 months Allowable Values shall be:

TSV-Closure: < 10% closed; and TCV Fast Closure, Trip Oil -Pressure-Low:

2 500 psig.

SR 3.3.4.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

SR 3.3.4.2.4 Verify TSV-Closure and TCV Fast Closure, 24 months Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29.5% RTP.

SR 3.3.4.2.5 -------------

NOTE-------------------

Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.2.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME 24 months on a is within limits.

STAGGERED TEST BASIS SR 3.3.4.2.6 Determine RPT breaker interruption time.

60 months I

PBAPS UNIT 2 3.3-31c Amendment No.

2, 247

Recirculacion Loops Operating 3.4 1 70 60 50 1

40 30 co 20 25 30 35 40 45 50 55 60 65 70 Core FP

(%Rated)

Figure 3.4.1-1 (page 1 of 1)

THERMAL POWER VERSUS CORE FLOW STABILITY REGIONS Amendment No. 210 247 PBAPS UNIT 2 3.4-5

EXELON GENERATION COMPANY. LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 250 License No. DPR-56

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated May 24, 2002, as supplemented by letters dated June 27, September 11, September 24, and October 16, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to paragraph 2.C.(1) of Facility Operating License No. DPR-56, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(1)

Maximum Power level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.

3.

The license is also amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 250, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

4.

This license amendment is effective as of its date of issuance, and shall be implemented upon startup following the Unit 3 14th Refueling Outage, currently scheduled for fall 2003.

FOR THE NUCLEAR REGULATORY COMMISSION IRA!

Ledyard B. Marsh, Acting Director Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to Facility Operating License No. DPR-56, page 3, and the Technical Specifications Date of Issuance: November 22, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 250 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Facility Operating License and the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Facility Operating License page 3 page 3 Technical Specifications 1.1-5 3.3-2 3.3-6 3.3-7 3.3-8 3.3-31 a 3.3-31 b 3.3-31 c 3.4-5 3.4-25 3.4-26 3.4-27 1.1-5 3.3-2 3.3-6 3.3-7 3.3-8 3.3-31 a 3.3-3 1 b 3.3-3 1 c 3.4-5 3.4-25 3.4-26 3.4-27

(5)

Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 3, at steady state reactor core power levels not in excess of 3514 megawatt thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

The Surveillance Requirements (SRs) listed in the licensee's letter dated August 4, 1995 are not required to be performed immediately upon implementation of Amendment No. 214. The SRs listed in the licensee's letter dated August 4, 1995 shall be successfully demonstrated prior to the time and condition specified below for each:

a)

Those SRs listed as Category A SRs in the licensee's August 4, 1995 letter shall be completed within a period consistent with the implementation date for Amendment 214, the specified frequency for each SR and the allowance of SR 3.0.2; b)

Those SRs listed as Category B SRs in the licensee's August 4, 1995 letter shall be completed within a period consistent with the last completion date for the related existing SRs, the specified frequency for each SR and the allowance of SR 3.0.2.

Page 3 Amendment No. 17, 53,130, 190, 201, 211, 214, 242, 250 Corrected by letters dated December 13, 1995, and February 5, 2001

Defn-nitions 1.1 A

1.1 Definitions PHYSICS TESTS (continued)

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3514 MWt.

The RPS RESPONSE TIME shall be that time interval from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 680F; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED TEST BASIS THERMAL POWER A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

(continued)

PBAPS UNIT 3 1.1-5 Amendment No. -244, 250

r.r insrnurmerL,

s 3.3.1.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more automatic C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Functions with RPS capability.

trip capability not maintained.

OR Two or more manual Functions with RPS trip capability not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B. or C not met.

the channel.

E. As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 29.5% RTP.

and referenced in Table 3.3.1.1-1.

F. As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G. As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

(continued)

I PBAPS UNIT 3 3.3-2 Amendment No. 214, 250

'l -

3..1.

i Z -

I 1

3.3.1.1I SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.1.13 Verify Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is

> 29.5% RTP.

SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 24 months 24 months

_r SR 3.3.1.1.15 Perform CHANNEL CALIBRATION.

24 months SR 3.3.1.1.16 Calibrate each radiation detector.

24 months SR 3.3.1.1.17 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months SR 3.3.1.1.18 Verify the RPS RESPONSE TIME is within 24 months limits.

I PBAPS UNIT 3 3.3 -6 Amendment No.

-34, 250

I -

i 1

3.3. 1.1 Table 3 3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation CUNUI I iUN

APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS 1

Wide Range Neutron Monitors REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D 1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

a.

Period-Short 2

5(a) 3 3

3 G

SR SR SR SR SR H

SR SR SR SR SR 3 3.1.1.1 3.3.1.1.5 3.3.1.1.12 3.3.1.1.17 3.3.1.1.18 3.3.1.1.1 3.3.1.1.6 3 3.1.1.12 3.3 1.1.17 3.3.1.1.18 2 13 seconds 2 13 seconds NA

b. Inop 2

G SR 3.3.1.1.5 SR 3 3.1.1.17 5(a) 3 H

SR 3.3.1.1.6 ZR 3.3.1.1 17 NA

2. Average Power Range Monitors

a. Neutron Flux-Hign (Setdown)

b. Simulated Thermal Power-High

c. Neutron Flux-Hligh

d. Inop

e. 2-Out-Of-4 Voter 2

1 1

1.2 1.2 3(c) 3(c) 3 1c) 3(c) 2 G

SR 3.3.1 1.1 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 F

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 F

SR 3 3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3 3.1.1.12 G

SR 3.3.1.1.11 G

SR 3.3.1.1.1 SR 3.3.1.1.11 SR 3.3.1.1.17 SR 3.3.1.1.1B s 15 0O RTP s 0.65 W

+ 63.7S RTP(b) and s 118.0S RTP s 119.7S RTP NA NA I

(continued)

(a) With any control rod withdrawn from a core cell containing one or tb) 0.65 W + 63.7S - 0.65 AW RTP when reset for single loop operation Operating.'

(c) Each APRM channel provides inputs to both trip systems.

more fuel assemblies.

per LCO 3.4.1. 'Recirculat1on Loops I

PBAPS UNIT 3 3.3-7 Amendment No. 2-34, 250

rrz) irib LI unlie:: uc Li ul

3. 3.1. 1 Table 3.3 1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D 1 REQUIREMENTS VALUE 3

Reactor Pressure -High 1.2 2

G SR 3 3 1 1 1 s 1085 0 psig

4.

Reactor Vessel Water Level-Low (Level 3)

5.

Main Steam Isolation Valve-Closure

6.

Drywell Prcssure -H~gh

7.

Scram Oischarge Volume Water Level -High 1,2 2

8 GSR SR SR SR G

SR SR SR SR SR F

SR SR SR SR G

SRZ SR SR SR SR G

SR SR SR SR 3 3.1.1 15 3 3 1.1.17 3 3.1 1.18 3.3.1.1.1 3.3.1.1.9 3.3.1.1.15 3.3.1. 1.17 3.3.1.1.18 3.3.1. 1.9 3.3

.1.1. 15 3.3.1 1.17 3 3.1.1.18 3.3.1.1.1 3.3.1. 1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1. 18 2 1.0 inches s 0l closed s 2.0 psig s 50.0 gallons 1.2 1.2 2

2 5(a) 2

8.

Turbine Stop Valve-Closure

9.

Turbine Control Valve Fast Closure. Trip Oil Pressure-Low

10.

Turbine Condenser -Low Vacuum

11.

Main Steam Line -High Radiation 2 29.5S RTP 4

2 29.5S RTP 1.2 2

2 2

H SR SR SR E

SR SR SR SR SR E

SR SR SR SR SR F

SR SR SR SR SR G

SR SR SR SR SR 3.3.1.1.9 3.3.1.1.15 3.3.1.1.17 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1. 1.18 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.18 3.3.1.1.1 3.3.1. 1.9 3.3.1.1.15 3.3.1.1.17 3 3.1.1.18 3.3.1.1.1 3.3.1.1.10 3.3.1.1.16 3.3.1.1.17 3.3.1.1.18 2 500.0 psig s 50.0 gallons s 101 closed I

I 2 23.0 Inches Hg vacuum

< 15 X Full Power

Background

12.

Reactor Mode Switch -

Shutdown Position 1.2 1

G SR 3.3.1.1.14 SR 3.3.1.1.17 H

SR 3 3.1.1.14 SR 3 3.1.1.17 NA 1

NA (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

PBAPS UNIT 3 3.3 -8 Amendment No. 2-4, 250

Lo,-J,- -. n sLr u~men ra z i 3 A

3.3.4.2 3.3 INSTRUMENTATION 3.3.4.2 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.2

a. Two channels per trip system for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

1. Turbine Stop Valve (TSV)-Closure; and

2. Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure-Low.

OR

b.

The following limits are made applicable:

1. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for inoperable EOC-RPT as specified in the COLR; and

2. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

limits for inoperable EOC-RPT as specified in the COLR.

APPLICABILITY:

THERMAL POWER 2 29.5% RTP.

I ACTIONS NOTE-------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A.1 Restore channel to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable.

OPERABLE status.

A.2

NOTE---------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

(continued)

PBAPS UNIT 3 3.3-31a Amendment No.

2299, 250

.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

1 B. One or more Functions with EOC-RPT trip capability not maintained.

B.1 Restore EOC-RPT trip capability.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Ii C. Required Action and associated Completion Time not met.

C.1 Remove the associated recirculation pump from service.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours OR C.2 Reduce THERMAL POWER to < 29.5% RTP.

SURVEILLANCE REQUIREMENTS NOTE-------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FRIEC FREQUENCY SR 3.3.4.2.1 Perform CHANNEL FUNCTIONAL TEST.

92 days (continued)

PBAPS UNIT 3 3.3-31b Amendment No. 2-2-, 2

Z. -Wr, ns:rumG<enaLion 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.4.2.2 Perform CHANNEL CALIBRATION. The Allowable Values shall be:

TSV-Closure: < 10% closed; and TCV Fast Closure, Trip Oil Pressure-Low:

> 500 psig.

SR 3.3.4.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST including breaker actuation.

FREQUENCY

+

24 months 24 months 24 months SR 3.3.4.2.4 Verify TSV-Closure and TCV Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 29.5% RTP.

I SR 3.3.4.2.5 NOTE-------------------

Breaker interruption time may be assumed from the most recent performance of SR 3.3.4.2.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME is within limits.

24 months on a STAGGERED TEST BASIS 60 months SR 3.3.4.2.6 Determine RPT breaker interruption time.

PBAPS UNIT 3 3.3 -31c Amendment No. 9-9. 250

RecircuSat tlon Loops Operating 3.4.1 7 (45, 70) 60 RESTRICTED e0 1(45,45.2)

~40 30 E

(20, 28.8)

UNRESTRICTED i-20

10 0

20 25 30 35 40 45 50 55 60 65 70 Core FIw (%Raed)

Figure 3.4.1-1 (page 1 of 1)

THERMAL POWER VERSUS CORE FLOW STABILITY REGIONS PBAPS UNIT 3

3. 4-5 Amendment No. 214 250

A

-D j

000-0 _

I I I l

l OF OF---T I11 1

I l Is

'-SIStGT<

o I

o 0

1 00

_00 j

G 4.00r 3..91 1pg f

Bo 2u,lpaur/rsue imtso 1 1 I I 22 E=?'Y EEL-iLNE CURVE 70S

-ESs UbM MflG -C 0 I I I DICOWINUIT' CtJrcE A 100 200 300 4-00

=-0 E30 MINIMUM REACTiOR VESSEL M-EV4. 7,E:MFE?--t7UFR (OF.,

Figure 3.4.9-1 (page I of 1)

Tempe-a-ure/Pressure LinuitS for Inservice Hydrostatic and :nservice leakage Tests PBAPS UNIT 3 3.4-25 Amendment No. 250

I 1 cO C-1 0

'Ir LI, 0-0 L.)

Ln U-120D 1000 BOO 600 400 200 I

II I

4 i iI i

I I I I 1 1!

I I I II I 1 i~

1 11 11 11 I i-r-11 1L. 1 I I I 17

-II I I ill I I I I i~

__L.O.SC.....I 1111 iT-

_1 22 1

j_

(EAYSE: CL rN' CVNZZE)

I I

I l i1l E, -NON-COnLW H.-L vP/

tII 2Lj

]

1 I 1 Gr2,v :-

/1 1 I

-Vi5sEc

^;Sc-.flT;x;Urnf I KTzI/

I acrrOU F'.

I.__

I!

IIOGSCONflNUfl UMES

/lL l__ I CUERVES EB A'IO 2, fRE VAUOD cOL1U0 t

/FOR 22 EFPY Cr CFrERAT10N l 0~F l/

22 EF?r BEL7LJNE CUP.Vc IS LESS UMmNG I-riAN

I l

DIOC0NTINUV~Y CUFRVE I

I 0

100 200 J00 400 500 Soo MINIMUM REACTOR VESSEL MF-AL TEMPERAURE

(°R)

Figire 3.4.9-2 (page 1 of 1)

Tefrpera ure/Pressure Linmts for Hcn-Nuclear HeatuD and Cooldown Following a Shutdown PBAPS UNIT 3 3.4 -26 Amendment No.

I I i

I 12100 100 Li)

EzoD 5

Lij z

FIGO L-i=

0*C0 Lij 700 I

I 1 !

1 1 i I I

I I I I 1 1i I I I I ! I I I i I I 111 1

I I ! I I 7 1 1 1 I 1 1 I 1 I I I I I 11 1 I 1 1 1I C -

NU'..l (c!

!C[

mC

!L I!L!I I

I Il I I I 111/71 I I ! ! /I C -

NUCLatR (CCP-C:U,,CI!I vZSE.. C4SCtSTiNPLr?

UMIT; CUJr'/E C S VAUO FCR 22

-F..-Y CF EPLTIN I 22 EFPY BELTUNE CURVrE I5 L35 UMnNC Tp.N DISCONfnNUrTY CU.rE C I

I !

I I A I Ill/UP

,Ot.71I I

I I

-I i 0

1D0 200

--CI 400 500 MINIMUM PEACTOR VEMBEL *ETAL TEUFE_.ATURE (OF)

igure 3. A.9 3 (page 1 of 1)

Temperaturei)reSsure Liri ts for Cri7.lcality PEAP suNlI T 3 3. -2 7 Arnendnent No. 250

For the safety evaluation associated with this document, please refer to ML031000317.

v t e Letter Sequence Approval
TAC:MB5192, (Approved, Closed) TAC:MB5193, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Withholding Request Acceptance, Withholding Request Acceptance Questions 12 August 2002 Answers 11 September 2002 Results Approval, Approval, Approval Other:
MONTHYEAR2002-08-12 [Table View]

Person / Time
ML031010365
Site:	Peach Bottom (DPR-044, DPR-056)
Issue date:	11/22/2002
From:	Boska J NRC/NRR/DLPM/LPD1
To:	Skolds J Exelon Generation Co, Exelon Nuclear
References
TAC MB5192, TAC MB5193
Download: ML031010365 (32)
v • d • e

ML031010365

Text

SUBJECT:

Dear Mr. Skolds:

Enclosures:

SUBJECT:

Dear Mr. Skolds:

Enclosures:

Attachment:

Background

Attachment:

Background

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